AIREMOD-RR is a point kinetics code which can simulate fast transients in nuclear research reactor cores. It can also be used for theoretical reactor dynamics studies. It is used for research reactor kinetic analysis and provides a point neutron kinetic capability. The thermal hydraulic behavior is governed by a one-dimensional heat balance equation. The calculations are restricted to a single equivalent unit cell which consists of fuel, clad and coolant.

For transient reactor kinetic calculations a modified Runge Kutta numerical method is used. The external reactivity insertion, specified as a function of time, is converted in dollar ($) unit. The neutron density, energy release and feedback variables are given at each time step. The two types of reactivity feedback considered are: Doppler effect and moderator effect. A new expression for the reactivity dependence on the feedback variables has been introduced in the present version of the code. The feedback reactivities are fitted in power series expression.

IAEA Safety and Licensing Guidebook of Research Core Conversion from the Use of High Enriched Uranium (HEU) to the Use of Low Enriched Uranium (LEU), Volume 3: Appendixes (G-H), Vienna, Austria (1990).

Research Reactor Core Conversion from the Use of High Enriched Uranium (HEU) to the Use of Low Enriched (LEU) Fuels Guidebook, IAEA-TECDOC-233 (1980).